Calculations of neutron fluxes and isotope conversion rates in a thorium-fuelled MYRRHA reactor, using GEANT4 and MCNPX
نویسندگان
چکیده
Neutronics calculations have been performed of the MYRRHA ADS Reactor with a thorium-based fuel mixture, using simulation programs MCNPX (Waters, 2002) and Geant4 (Agostinelli, 2003). Thorium is often considered for systems, this first evaluation possibilities thorium based fuels reactor design which has developed in detail. It also extends application widely-used program to geometry thorium. An asymptotic 232Th/233U mixture considered, together standard MOX possible 232Th/MOX starter. Neutron fluxes spectra are calculated at several regions core: cells, IPS cells two (Mo Ac) isotope production cells. These then used simple evolution potential incineration minor actinide waste. Results from agree support each other show that viable, good evolution/breeding properties, incineration, though it will not take place on significant scale, be demonstrable.
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ژورنال
عنوان ژورنال: Nuclear Engineering and Design
سال: 2022
ISSN: ['0029-5493', '1872-759X']
DOI: https://doi.org/10.1016/j.nucengdes.2021.111629